1-7 of 7
Yupeng Cao
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020
Paper No: ICONE2020-16261
DOI: https://doi.org/10.1115/ICONE2020-16261
View Paper
PDF
Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Chinese RPV Steels

Yupeng Cao, Yinbiao He, Binxi Wang, Yifeng Huang, Hui Li, Yan Yu, Hu Hui
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A028, July 14–19, 2019
Paper No: PVP2019-93615
DOI: https://doi.org/10.1115/PVP2019-93615
View Paper
PDF
Topics: Embrittlement, Irradiation (Radiation exposure), Steel, Forging, China, Fluence (Radiation measurement), Fracture toughness, Mechanical properties, Notch testing, Nuclear power stations
Proceedings Papers

Constraint Assessment for Cruciform Specimens With a Semi-Elliptical Crack

Yupeng Cao, Guian Qian, Yinbiao He, Yuh J. Chao
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A034, July 15–20, 2018
Paper No: PVP2018-84427
DOI: https://doi.org/10.1115/PVP2018-84427
View Paper
PDF
Topics: Fracture (Materials), Stress, Fracture toughness, Materials properties, Engineering simulation, Finite element analysis, Finite element model, Hardening, Mechanical properties, Simulation
Journal Articles

Constraint Assessment for Specimens Tested Under Uniaxial and Biaxial Loading Conditions

Yupeng Cao, Guian Qian, Yinbiao He, Markus Niffenegger, Yuh J. Chao
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. June 2018, 140(3): 031401.
Paper No: PVT-17-1150
DOI: https://doi.org/10.1115/1.4039346
Published Online: April 3, 2018
View Article
PDF
Topics: Fracture (Materials), Stress, Finite element analysis, Fracture toughness
Proceedings Papers

Constraint Assessment for Specimens Tested Under Uniaxial and Biaxial Loading Conditions

Yupeng Cao, Guian Qian, Yinbiao He, Yuh J. Chao, Markus Niffenegger
Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A049, July 16–20, 2017
Paper No: PVP2017-65979
DOI: https://doi.org/10.1115/PVP2017-65979
View Paper
PDF
Topics: Design, Engineering simulation, Finite element analysis, Fracture (Materials), Fracture toughness, Materials properties, Reactor vessels, Simulation, Stress, Tension
Proceedings Papers

Further Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Yupeng Cao, Yinbiao He, Hui Hu, Hui Li
Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A039, July 17–21, 2016
Paper No: PVP2016-63799
DOI: https://doi.org/10.1115/PVP2016-63799
View Paper
PDF
Topics: Reactor vessels, Thermal shock, Fracture (Materials), Fracture mechanics, Design, Nuclear engineering, Nuclear power stations, Phase transition temperature, Transients (Dynamics)
Proceedings Papers

Re-Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Yupeng Cao, Yinbiao He, Hu Hui, Hui Li, Fuzhen Xuan
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A033, July 19–23, 2015
Paper No: PVP2015-45577
DOI: https://doi.org/10.1115/PVP2015-45577
View Paper
PDF
Topics: Reactor vessels, Thermal shock, Accidents, Coolants, Design, Fracture (Materials), Transients (Dynamics), Cladding systems (Building), Nuclear engineering, Nuclear power stations